Tungsten monoblock concepts for the Fusion Nuclear Science Facility (FNSF) first wall and divertor

Huang, Y.; Tillack, M. S.; Ghoniem, N. M.

doi:10.1016/j.fusengdes.2017.06.026

Tungsten monoblock concepts for the Fusion Nuclear Science Facility (FNSF) first wall and divertor

Journal Article · Fri Jun 23 00:00:00 EDT 2017 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2017.06.026· OSTI ID:1609493

Huang, Y. ^[1]; Tillack, M. S. ^[2]; Ghoniem, N. M. ^[3]

Univ. of California, Los Angeles, CA (United States); DOE/OSTI
Univ. of California, San Diego, CA (United States)
Univ. of California, Los Angeles, CA (United States)

Next-step fusion nuclear devices require plasma-facing components that can survive a much higher neutron dose than ITER, and in many design concepts also require higher operating temperatures, higher reliability, and materials with more attractive safety and environmental characteristics. In search of first wall concepts that can withstand surface heat fluxes beyond 2 MW/m², we analyzed advanced “monoblock” designs using coolants and materials that offer more attractive long-term performance. These use tungsten armor and heat sinks, similar to previous designs, but replace the coolant with helium and the coolant containment pipe with either low-activation ferritic-martensitic steel or SiC/SiC composite. The results of analysis show that helium-cooled steel can remove up to 5 MW/m² of steady-state surface heat flux and helium-cooled SiC/SiC can remove nearly 10 MW/m² while satisfying all materials and design requirements. This suggests that a He-cooled W/SiC monoblock could withstand divertor-like heat fluxes.

View Accepted Manuscript (DOE)

Research Organization:: Univ. of California, Los Angeles, CA (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: FG02-03ER54708

OSTI ID:: 1609493

Alternate ID(s):: OSTI ID: 22850340

Journal Information:: Fusion Engineering and Design, Journal Name: Fusion Engineering and Design Journal Issue: B Vol. 135; ISSN 0920-3796

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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